RELAP5/MOD2 assessment, OECD-LOFT small break experiment LP-SB-03
Creators
- 1. Paul Scherrer Inst., Wuerenlingen (Switzerland)
Description
An analysis of the experimental results and post-test calculations using RELAP5/MOD2 carried out for OECD-LOFT small break experiment LP-SB-3 are presented. Experiment LP-SB-3 was conducted on March 5, 1984 in Loss-of-Fluid Test (LOFT) facility located at the Idaho National Engineering Laboratory (INEL). The experiment simulated a small cold leg break, with concurrent loss of high pressure injection system, and cooldown and recovery by feed and bleed of the steam generator secondary side and accumulator injection, respectively. The analysis was under taken as a part of a program at EIR aimed at developing experience in using the latest generation of best estimate Loss of Coolant Accident (LOCA) analysis computer codes, and to improve understanding of Small Break LOCA transients and as well as a part of a program aimed at assessing the RELAP5/MOD2 code. The latest available version (Cycle 33 to 36.1) of the code was used. The particular test selected for the analysis included several phenomena potentially relevant to any PWR plant operation in Switzerland. This report documents a short post-test analysis of the experiment emphasizing the results of additional analysis performed during the course of this task. RELAP5/MOD2 input model and results of the post-test calculation are documented. Included in the report are the results of a sensitivity analysis which show the predicted thermal-hydraulic response to a different input model. 7 refs., 55 figs., 2 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A05/MF A01 - GPO as TI90010669; OSTI; INIS.
Files
Additional details
Publishing Information
- Imprint Pagination
- 88 p.
- Report number
- NUREG/IA--0018
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21068196
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CLADDING; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; FAILURE MODE ANALYSIS; FLUID FLOW; FUEL ELEMENTS; HEAT TRANSFER; HOMOGENEOUS MIXTURES; HYDRAULICS; INTERNATIONAL COOPERATION; LEAKS; LOSS OF COOLANT; O CODES; PERFORMANCE TESTING; PIPES; PRESSURE DEPENDENCE; PWR TYPE REACTORS; R CODES; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; RISK ASSESSMENT; STEAM GENERATORS; SWITZERLAND; THERMODYNAMICS; TRANSIENTS; US DOE; VAPORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; COOLING SYSTEMS; COOPERATION; DEPOSITION; DEVELOPED COUNTRIES; DISPERSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; EVALUATION; FLUIDS; GASES; MIXTURES; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SURFACE COATING; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; THERMAL REACTORS; US ORGANIZATIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS